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Evaluation of Zirconium Hydride as Moderator in Integral, Boiling Water-Superheat Reactors
This report summarizes the results and conclusions of a study made to evaluate the merits of using zirconium hydride as a solid moderator in an integral boiling water-nuclear superheat reactor of the pressure vessel type.
Date:
March 1, 1962
Creator:
Gylfe, J. D.; Rood, H.; Greenleaf, J.; Balkwill, K.; Prem, L. & Goldfisher, L.
System:
The UNT Digital Library